B213 VOID FRACTION DISTRIBUTIONS OF AIR-WATER TWO-PHASE FLOW IN A ROD BUNDLE MEASURED BY NEUTRON RADIOGRAPHY(Nuclear power-3)
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概要
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Quantitative void fraction measurement methods based on the umbra method using a neutron absorber grid were applied to the void fraction measurement of two-phase flow in a 4x4 rod bundle. The grid 3mm in width and 3mm in interval was made from B_4C. The two-phase flow direction was vertical and the rods of the grid were placed horizontally between the rod bundle and the neutron source. A cooled-CCD camera in the JRR-3M thermal neutron radiography system was used. Cross sectional averaged one-dimensional void fraction distributions along the flow direction were calculated with 3mm interval. Quantitative measurement with spatial resolution 0.18mm, the size of the image element, horizontally and 3mm, the interval of the grid vertically was carried out.
- 一般社団法人日本機械学会の論文
- 2000-10-01
著者
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Fujii Terushige
Department Mechanical Of Engineering Kobe University
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Takenaka Nobuyuki
Department Mechanical Of Engineering Kobe University
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Asano Hitoshi
Department Of Mechanical Engineering Kobe University
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Maeda Norio
Department Of Mechanical Engineering Kobe University
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Maeda Norio
Department Of General Foods The Hokuren Federation Of Agriculture Corporation
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HAYAMA Shunsuke
Department of mechanical Engineering, Kobe University
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Hayama Shunsuke
Department Of Mechanical Engineering Kobe University
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Asano Hitoshi
Department Of Applied Chemistry Faculty Of Engineering Gunma University
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TAKENAKA Nobuyuki
Department of Mechanical Engineering, Kobe University
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Maeda Norio
Department of Chemistry, Faculty of Science, Hokkaido University
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